On the account for kinetic effects when calculating local neutron-physical characteristics in fast reactor cores

The possibility of refinement of local neutron-physical characteristics of fast reactor cores by means of combination of calculations in diffusion approximation with kinetic equation solution in the isolated region is investigated. On the base of the analysis of the results of one-dimensional numerical experiments it is shown that for refining local neutron-physical characteristics of fast power reactors in many cases it is sufficient to use combination of the calculation in diffusion approximation over the reactor with kinetic equation solution in the isolated regions with boundary conditions from the calculation in diffusion approximation. Discordance in the results of such calculation with the results of kinetic equation solution over the reactor is approximately by an order less than the error of the initial calculation in diffusion approximation. The methods suggested can be carried over to the case of three-dimensional hexagonal or trigonal geometry